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2012_Lessons learned from the SRA preparation

18/10/2012

255 KB

ANNETTE 2017 List of learning outcomes of ANNETTE WP2 courses

The report, published in May 2017 (CIRTEN Report No. MR/ANH2020/012017 Version 1), summarises the information on ANNETTE WP2 courses in terms of learning outcomes as collected up to the date of writing (mid-January 2017).

CAST - This report provides a review of the current status of knowledge on various aspects related to the release of 14C from zirconium alloys waste (hulls), which is of importance for long-term safety analyses of final repositories for long-lived Intermediate level waste.

CAST 2015 D2.1 State of the art review of steel corrosion and C14 release

CAST - The objective of this report is to review the current state of understanding of steel corrosion rates and carbon-14 releases from irradiated steels under conditions relevant to the storage and long-term disposal of radioactive wastes and thereby incorporate information available from outside the CAST project into CAST WP2.

CAST - A state of the art review on the different techniques used to characterize spent ion exchange resins is presented. A large part of the works that were done so far are based on liquid scintillation counting, but an increasing amount of determination are now performed in accelerator mass spectrometry. Other non-conventional techniques are also reviewed. Finally, a status of knowledge is provided on the possible chemical forms (speciation) under which 14C can be released from spent ion exchange resins. Analytical strategies for speciation by partners are also described. Available estimations of the proportion of inorganic vs. organic forms are reviewed as well as the possibility of the different forms of organic molecules, and gaseous release.

CAST 2015 D5.5 Review of current understanding of inventory and release of C14 from irradiated graphite

CAST - To ensure knowledge and understanding from the CARBOWASTE project is thoroughly considered in the CAST project, Task 5.1 is being undertaken in the first year of CAST. This task is the subject of the current report, and has the aim to review CARBOWASTE and other relevant R&D activities to establish the current understanding of inventory and release of carbon-14 from irradiated graphites.

CAST - This report presents information on graphite characterisation as is being undertaken as part of the Chernobyl Nuclear Power Plant Decommissioning Program. Work considering chemical decontamination of graphite is reported, as is the overall graphite waste management approach.

CAST - The main objective of the IFIN-HH in the second year of its input to Work Package 5 was to update the inventory of 14C in the irradiated graphite arising from thermal column of VVR-S Reactor and radioactive wastes containing organic and inorganic 14C compounds. IFIN-HH has characterized the 14C inventory of irradiated graphite from thermal column of VVR-S Reactor, and has started to develop a method, based on the use Accelerator Mass Spectrometry (AMS) which will be suitable to characterize the distributions of14C inventory in irradiated graphite. Finally, in order to measure the total release of 14C (and 3H) to solution and gas from crushed and intact i-graphite from the VVR-S Reactor, the experimental apparatus has been designed and manufactured.

CAST 2016 D5.8 Synthesis report on 14C speciation in solution and gas from French graphite waste

CAST - Carbon 14 is one of the key radionuclides for the future disposal of French irradiated graphite waste. It is one of the main long-lived radionuclides, and depending on its speciation, it can be more or less mobile in a disposal facility and more or less incorporated into living organisms. Following a first report concerning a review of the available leaching data of French irradiated graphite, particularly focused on carbon 14 release rates (D5.1), this second report (D5.8) addresses the speciation of the released carbon 14.

CAST - The first phase of WP6, prior the analysis of the experimental results delivered by the project, aims at taking stock of the C-14 knowledge from the angle of safety assessments. Deliverable D6.1 gives an overview on this for each national program. On the basis of this compilation, commonalities and differences between disposal concepts regarding the impact of the uncertainties linked to C-14 release from radioactive waste disposal will be identified as well as the way to cope with them. This thorough discussion will be the object of deliverable D6.2.

CAST - In this report the work performed by the Karlsruhe Institute of Technology (KIT) with support from the National Cooperative for the Disposal of Radioactive Waste (NAGRA, Switzerland) within the work package 2 of the CAST project is summarized. In the following sections, the thermodynamic modelling of 14C in metals is presented as well as the experimentally determined 14C inventory in irradiated steel and the chemical form of 14C released from the studied material.

CAST - The aim of the work at SCK•CEN in the framework of Work Package 2 of the CAST project was to investigate the release of 14C from carbon steels representative for the reactor pressure vessel (RPV) steel of Belgian nuclear power plants and the 14C speciation in a cementitious environment, which is relevant for the Belgian geological disposal concept, which involves placing the RPV steel in a concrete monolith.

CAST - This report is deliverable D2.8 of the CAST project. In this deliverable, the details about the experiments focusing on the study of C-14 release form irradiated steel are presented. It includes the samples, experiment design, description of analytical methods, experiment and its results, and discussions of the results. This deliverable describes results up to 5 months of running the experiment.

CAST 2017 D5.11 Report on exfoliation processes and on structural and morphological properties

CAST - In this deliverable, the behaviour of nuclear graphite through the exfoliation process has been studied, carried out with different organic solvents to remove primarily radiocarbon and estimate the “Removal Efficiency“ (as percentage of the recovered activities after treatment in comparison to the original values) of the used solvents in order to propose a reliable approach to produce graphite for recycling or/and safety disposed as L&ILW.

CAST 2017 D5.12 Final evaluation of leach rates of treated and untreated i-graphites

CAST - Work Package 5 of the EC CAST project considers the behaviour of 14C i-graphite. In particular, the work is focused on understanding the factors determining the release of 14C from irradiated graphite (hereafter “i-graphite") under disposal conditions (including surface disposal facilities and deep geological disposal facilities). In this study, the release of 14C was investigated in model experiments with i-graphite from the Rossendorf Research Reactor (RFR).

CAST - Irradiated graphite, dismantled from the thermal column of VVR-S Reactor, contains different radioisotopes as activation products, including carbon-14 (C-14) and tritium (H-3). In repository-relevant conditions, this graphite could be a source of gases containing C-14 and H-3. In the experiments performed by IFIN-HH we have investigated the release of C-14 and H-3 from two intact samples of irradiated graphite which have been cut from the thermal column disc located near the reactor core.

CAST - The development of both analytical methods and protocols to measure the release of 14C from irradiated graphite samples and the speciation in the aqueous and gaseous phase has been performed throughout the CAST project. Analytical methods, suited to identify and quantify low molecular weight organic molecules, comprise Ion Exchange Chromatography and Gas Chromatography coupled to Mass Spectrometry, they are described for aqueous and gaseous samples. Also, the preparation of the leaching experiments to measure the release of 14C is described in this report.

CAST - This report is one of the CAST Work Package 5 (WP5) deliverables and it presents results of Lithuanian Energy Institute (LEI) activities performed in the Task 5.2 “Characterisation of the C-14 inventory in i-graphites”.

CAST - The aim of work undertaken by IPNL is to simulate the behaviour of 14C during reactor operation and evaluate the independent or synergistic effects of temperature and irradiation on 14C behaviour.

CAST - Work Package 6 of the CAST project is devoted to the knowledge base concerning the re-lease and transport of 14C in the context of post-closure safety assessments of the geological disposal of radioactive waste. This report (D6.2) assesses the various approaches for safety assessment discussed in report D6.1 in the light of the existing knowledge about the 14C source term. It proposes a synthesis of D6.1, identifies commonalities and differences between approaches and concepts and highlights safety-critical uncertainties pertaining to 14C fate in waste disposal.

Cebama deliverable D1.03, published March 2016.
This report is an initial state-of-the-art literature review in the CEBAMA–project for work package 1. Chapters are written by the participants of CEBAMA and the chapters serve as state-of-the-art reviews for the the experimental research conducted by various partners.

Cebama 2016 D3.04 Description of and results from the modelling of external lab and/or field experiments

Cebama deliverable D3.04, published December 2016.
The present deliverable D3.04 contains a description of modelling approaches and recent progress by WP3 partners and summarises the results of the modelling of existing experimental datasets. Given that experimental results in CEBAMA will become available later in the project, preliminary work in WP3 has thus been focused on the development and implementation of models and on the simulation of existing experimental datasets.
Each partner contribution below summarises the modelling work so far, with application to existing experiments, using a similar approach to the one proposed to analyse experimental data generated in CEBAMA. In some cases, the efforts so far have been devoted mainly to the development of the modelling tools.

Cebama deliverable D4.09, published January 2017.
This report series aims at interpreting how the results of the research conducted within CEBAMA can be applied and contribute to the Safety Case. This is the first
of two reports, which will be updated at the end of the project. Given the complexity of the experiments and the models developed within CEBAMA, it is in general too early at PM18 for the partners to produce results directly applicable to the Safety Case. Nevertheless, we present here some briefing on the impact aimed at within the project and highlight the value of some of the work undertaken to date.

The Deployment Plan2011- 2016, final version June 2012 is now available !
The goal of the deployment of the activities flowing from the SRA is to assist the IGD-TP Executive Group members and participants in achieving the vision and the desired results by joint RD&D activities during the next years.

IGD-TP_2011_Public consultation comments and responses on draft SRA document version December 23, 2010

8/08/2012

454 KB

IGD-TP_2011_Strategic Research Agenda

8/08/2012

3 MB

IGD-TP_Master Deployment Plan 2015

2/10/2015

4 MB

IGD-TP_Vision Document

2/08/2016

10 MB

IGD-TP/SNETP factsheet

27/04/2015

167 KB

JOPRAD 2016 Dissemination Strategy (Deliverable D6.1)

Dissemination Strategy (Deliverable D6.1) published May 2016.
The JOPRAD Dissemination Strategy is a strategic document establishing the bases for the dissemination of the project activities in order to enhance the impact of JOPRAD and achieve a high-level of engagement. This key deliverable of WP6 summarises the strategy and concrete actions related to the communication and dissemination of the project activities and outcomes. It is the key document of reporting on project progress as agreed with the EC.

Report of the JOPRAD Mid-Term Workshop (MTW) held on 7- 8 September 2016 at the Congress Centre, Prague, Czech Republic. The Mid-Term Workshop (MTW) enabled “programme owners” and “programme managers” in European Union (EU) Member-States (MS) to evaluate the feasibility and the added-value of the implementation of Joint Programme at the European level.

JOPRAD 2017 Draft Programme Document for public consultation (Work Package 4, Deliverable D4.2, v0.7, March 2017).
This Programme Document sets out the scientific and technical basis of a future Joint Programme on Radioactive Waste Management and Disposal. In its current form, it is a deliverable of the EC ‘Towards a Joint Programme on Radioactive Waste Disposal - JOPRAD’ project and represents the views of JOPRAD participants on research, development and demonstration (RD&D) priorities considered as suitable for Joint Programming. To obtain the support of the wider European Radioactive Waste Community, the contents herein will be disseminated and the draft document made available for open consultation during March – April 2017. Finalisation and issue to the European Commission is expected by the end of November 2017. After this time, it is anticipated that this Programme Document (in its final form of a Strategic Research Agenda) will be taken over in-part or wholly by those responding to the European Commission EURATOM H2020 Call (WP2018) in the form of a Joint Programme Proposal.

MIND 2015 D1.1 A Review of Anthropogenic Organic Wastes and Their Degradation Behaviour

MIND Deliverable D1.1, published December 2015.
Work Package 1 of the MIND project addresses remaining key issues for the geological disposal of ILW concerning the long-term behaviour, fate and consequences of organic materials in the waste along with H2 generated by corrosion and radiolysis. This review begins this work by collating information concerning the inventory and nature of organic materials present in ILW and some LLW that requires geological disposal. The review has then considered the physical and chemical conditions that the organic materials will be subjected to during storage and geological disposal. The review then provides a summary description of the physical and chemical nature of the main organic materials present in ILW and their known chemical and radiolytic degradation behaviour. The effect of the organic degradation products on radionuclide speciation, which could affect how some radionuclides are transported in groundwater, is then considered to focus subsequent work in this field.

MIND Deliverable D2.1, published November 2016.
In order to provide data needed to address the question on geochemical constraints of biological activity at spent nuclear fuel waste repository sites, geochemical data of dissolved gases from deep drill holes and mines in Finland and Sweden were collected based on a literature and database survey. Gas data were found from 20 separate localities in Finland with the deepest drill holes extending down to 2500 m below surface. The gas phase is dominated by nitrogen and methane, although significant variation exists between different sites and with depth. At least partly this variation can be related to differences in lithology (rock types) and residence time of water within the bedrock. Corresponding data from Sweden were from 2 localities extending to at most 1000 m below surface.

MIND deliverable D3.1 published October 2016.
This year one evaluation report of MIND consists of two parts. The first part is a description of the state of the art of geological disposal of radioactive waste, with a special reference to microbiological issues. The second part is the first year evaluation of the microbial processes studied in MIND Work Packages 1 and 2.

MIND Deliverable D3.3, published November 2016.
The overall aim of both the education and training initiatives in MIND is to cultivate awareness of the relevance of microbial issues in otherwise typically abiotic fields of
expertise, and dissipate the knowledge gained in the MIND project beyond the known geomicrobiology expert circles. For this reason, modular training courses were developed, an exchange programme for Master and PhD students has been developed and focused communication on these initiatives has been undertaken.

MIND Deliverable D2.3, published August 2017.
Geochemical data on sulphur compounds and dissolved gases from deep drill holes and deep mines in Finland were compiled into a database. Data is used as
background for MIND work package 2, in which microbial production of sulphide in the geosphere will be assessed from the point of view of canister corrosion. This report summarises the present knowledge on the mode of occurrence of sulphur compounds and dissolved gases in groundwaters of crystalline bedrock. Prerequisites
of microbial sulphate reduction are discussed based on the data available.

MIND Deliverable D2.4, published June 2017.
It has been hypothesised that cut-off bentonite density thresholds exist above which all bacterial activity stops or is inhibited to a such a level that it can be regarded as negligible. This report discusses if that hypothesis can be considered true or if more variables other than clay density determine bacterial activity in bentonites. The clays analysed and discussed in this report have been investigated previously. This deliverable summarizes previously performed work and new work performed within MIND.

MIND deliverable D3.4 published July 2017.
This report is a synthesis of the outcome of the experimental and modelling research activities in MIND WP1 and WP2, performed over the first 2 years of the project. The scope of the report is broad, covering all completed scientific and ‘in progress’ projects contained within MIND. The emphasis in this report is on the description of the degradation processes that can be expected and the environmental boundary conditions under which they can occur. The kinetics of these processes are not featured prominently here, but will become an increasingly prioritised aspect of the MIND project throughout the remainder of its tenure, and a next update of this report.

Deliverable D2.1 is the summary report for Task 2.1 of Work Package 2, which is focused on monitoring programme design basis, monitoring strategies and decision making. This task aimed to address several remaining generic issues not previously addressed in international collaborative projects. D2.1 addresses these through undertaking work related to the following objectives:
- Evaluate the role of monitoring within the post-closure safety case.
- Evaluate high-level monitoring strategies.
- Consider the range of decisions to be made during repository implementation that will require information from monitoring.
- Develop screening methodologies used to develop monitoring parameter lists for different national monitoring contexts.